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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Hyung Kook Joo, Chang Hyo Kim, Jae Man Noh, Si-Hwan Kim
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 300-312
Technical Paper | doi.org/10.13182/NSE94-A18989
Articles are hosted by Taylor and Francis Online.
New core-reflector boundary conditions designed to replace the explicit representation of the reflector in nodal computations are developed taking into account the transverse leakage in the reflector region. Two approximations are introduced for the transverse leakage in the reflector region: exponential approximation for the slab reflector and quadratic polynomial and exponential approximation for the L-shaped reflector. Core-reflector boundary conditions that relate net current with flux at the core-reflector interfaces are then derived by solving the transverse integrated neutron diffusion equation with transverse leakage approximations in the reflector region. To test the usefulness of new core-reflector boundary conditions, nodal expansion method computations with and without explicit representation of reflectors are performed for the core power distribution and criticality of Zion-1 and YGN-1 pressurized water reactors. It is demonstrated that core power and criticality computations with new boundary conditions agree very well with those with the reflector included explicitly in computational nodes.